ML20151R028

Discusses QA for CESSAR-DC,Sys 80+ & Significant Points Made Listed

ML20151R028
Person / Time
Site:	05000470
Issue date:	08/02/1988
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
PROJECT-675A NUDOCS 8808120030
Download: ML20151R028 (5)

Text

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%*c UNITED STATES y h NUCLEAR REGULATORY COMMISSION

$ $ WASHINGTON, D. C. 206f6 e

% . . . . . #' August 2, 1988 Project No. 675 Mr. A. E. Scherer, Director Nuclear U censing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

SUBJECT:

QUALITY ASSURANCE FOR CESSAR-DC, SYSTEM 80+

By letter dated May 25, 1988, you responded to 6 of 22 items regarding QA for CESSAR-DC which were transmitted to you by our letter of February 26, 1988.

In your letter you indicated that the response to the other 16 items will be provided to the NRC by the third quarter of 1988 in a revised QA program description.

We have reviewed your response to the 6 items and discussed them with Combustion Engineering personnel by telephone. The significant points that were made are as follows:

Item Comment 260.1 The response should be tied to CENPD-210A and/or the CESSAR Design Certification SAR 260.2 The response should referance CENPD-210A for the QA responsibilities of C-E's engineering organizations 260.4 Response is acceptable 260.5 Response is acceptable 260.6 Chapter 17 of the SAR should indicate where QA for fire protection is addressed is the SAR 260.10 We agreed to look again at the request for additional information, and have done so. Enclosure 1 provides our suggested C-E commitment to 10 CFR 50.55 since there is no construction permit holder that would be required to meet a comparable comitment.

8808120030 880802 (j PDR ADOCK 050g4 O }

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Mr. A. E. Scherer We assume that the above comments will be considered in the revised program description to be submitted in the third quarter of 1988.

The correlation between the requests for additional information and the latest revision of the Standard Review Plan (NUREG-0800) was also discussed. Your personnel appeared to be satisfied with the relationship to the request for additional information.

Sincerely.

C',

S. Vissing, oject flanager

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Gu Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

cc: See next page

. Ar. A. E. Scherer August 2, 1988 We assume that the above comments will be considered in the revised program description to be submitted in the third-quarter of 1988.

l The correlation between the requests for additional information and the latest l revision of the Standard Review Plan (NUREG-0800) was also discussed. Your i personnel appeared to be satisfied with the relationship to the request for additional information.

Sincerely, 1

Original Signed By:

I Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects

( Office of Nuclear Reactor Regulation l

Enclosure:

cc: See next pago Distribution:_,,,

' Docket File u S EHylton B(rimes l NRC PDRs GVissing ACRS (10) {

PDSNP Reading OGC-Rock. SWeiss DCrutchfield Edordan JSpraul PDSN PDSNP CM GVissing Chiller 08/f /8e 08/ L/88

. Combustion Engineering, Inc. Project No. 675 Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue, Suite 1310 Bethesda,Itu yland 20814 Dr. Michael Green Manager of Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500

' Windsor, Connecticut 06095-0500

ENCLOSitRE 1 10 CFR 50.55 Requirements (e)(1) C-E shall notify the NRC of each deficiency found in design which, were it to have remained uncorrected, could have affected adversely the safety of operations of t. ) nuclear power plant at any time throughout the expected ifetime of the plant c d which represents a significant breakdown in any e

portion of the QA program conducted in accordance with the requirements of Appendix B.

(e)(2) #

-E shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the NRC of each reportable

ficiency.

(e)(3)(1) C-E shall ako submit, as specified in %50.4, twrittM report on a reportuole deficiency within 30 days.

(11) The repe t must include a description of the deficiency, an analysis of the safety implications and the coirective action taken, and suffic'ent information to permit analysis and evaluation of the deficiency and of the corrective action. If sufficient information is not available for a definitive report l to be submitted within 30 days, an interim report containing all l available information shall be filed, as specified in %50.4, together with a statement that indicates when a complete report wili be filed. 1 (f)'l) C-E shall implement, pursuant to %50.34(a)(7), the QA program described or referenced in the SAR, including changes to that i report.

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